ML18227A271

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Semiannual Report of Radioactive Effluent Releases and Environmental Radiological Monitoring for Period July 1, 1977 Through December 31, 1977
ML18227A271
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 02/27/1978
From:
Florida Power & Light Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML18227A271 (149)
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Text

TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUAL REPORT OF RADIOACTIVE EFFLUENT RELEASES AND ENVIRONMENTAL RADIOLOGICAL MONITORING FOR PERIOD JULY 1, 1977 THROUGH DECEMBER 31, 1977 IN COMPLIANCE WITH TECHNICAL SPECIFICATION 6,9,4 Boctrot rcjgocp roc'c'f Control z->I o'toto of Oocumont:

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s 1 INTRODUCTIONs s s s s s s s s s a s s s s s s s s s s s 2 (A) RADIOACTIVE EFFLUENT RELEASES s s s s s s s s s s s s s s (j ) LIQUID RELEASES ~ ~ s s 3 (2) AIRBORNE RELEASES s s ~ ~ ~ s s ~ s 13 (3) SO!ID WASTE BURIALs s s s s s s s s s s s s s s 19 (B) RADIOLOGICAL ENVIRONMENTAL MONITORING s s s s s s a s s s 20 CORRECTED COPY OF PAGE I OF A I RBORNE SECT I ON ~ s s s s s 32

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THIS REPORT IS SUBMITTED IN ACCORDANCE WITH TURKEY POINT PLANT TECHNICAL SPECIFICATION SECTION 6i9,4, THIS REPORT COVERS THE DATA NECESSARY TO MEET THE SEMI-ANNUAL REPORTING REQUIREMENTS FOR (A) RADIOACTIVE EFFLUENT RELEASES AND (B) ENVIRONMENTAL RADIOLOGICAL NON ITORING e FOR THE PERIOD OF JULY li THROUGH DECEMBER 3lg 1977

I Radioactive Effluent Releases All liquid and airborne discharges to the environment. durin'g this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Safety Guide 21 has been met or exceeded.

Li uid Releases Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2m gas flow proportional counter. The efficiency of the gas flow proportional counter

.is adjusted so that the..activity. determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste .

disposal system and for secondary system batch releases. Frequent periodic sampling and analysis were used to conservatively estimate the quantity of radioactivity released via the steam generator blowdown system.

The following comments will aid in the interpretation and evaluation of the liquid release data presented in Table I, pages 1 through 7:

1. The reported values in Table I, page 1, include in their computation the quantity of radioactivity released from both the waste disposal system and the secondary system. The secondary system releases occurred when contaminated water was blown down from the steam generators during primary to secondary leakage conditions, or when the generators were drained for repair or refueling, or during lancing of the generators.
2. The reported values in Table I, pages 2 and 3 are the total quantities of radioactivity for individual nuclides released from the waste disposal system and the secondary system together. The values in Table I, page 4 are for the waste disposal system only and pages 5 and 6 are for the secondary system-only.. During primary to secondary leakage, release of several short-lived nuclides occurred from the secondary system. These short-lived nuclides are not generally detected in batch releases from the waste disposal system due to the long holdup time of'processed water.
3. Only those isotopes that were detected in the secondary system releases were reported. All non-detectable isotopes are listed as

(.) ~

4. Weekly and monthly composite samples for the'waste disposal system were prepared to give a proportional weight to each liquid release made during the designated period of accumulation. The composites were analyzed for gamma emitting isotopes on a multichannel analyzer attached to a high resolution Ge(Li),.detector, and for Sr-89 and ~

, Sr-.90,,using a chemical separation and subsequent beta determination with a 2m gas flow proportional counter. Tritium was determined by us'e of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2n gas flow proportional counter. All concentrations for radioactivity determined'rom analysis of a composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

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5. At least one representative batch of liquid effluent from the waste disposal system was. analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released for the month in order to estimate the total dissolved gases released.

If more than one batch of effluent was analyzed, the concentrations are weighted in an appropriate manner. The results are totaled on a monthly basis in Table I, page 7. Dissolved gases from secondary system releases were determined from the samples. of the individual releases. Isotopic concentrations were multiplied by the volume released to determine the quantity of radiogas nuclides released.

6. Representative samples of secondary system batch releases were analyzed individually for gamma emitting isotopes and by analysis of a representative composite for tritium, gross alpha and selected beta emitters.
7. The applicable limit for release of radioactive material in liquid waste is five curies per quarter.
8. The following notes have been added to help explain some of the results in Table I which have been superscripted with a lower case letter:

Su erscri t Notes The Q/MPC for this release was 0.11.

The Q/MPC for this release was 0.046.

The Q/MPC for this release was 0.018.

No primary to secondary leakage was occurring; therefore, most short-lived isotopes were not present.

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Table I Report of Radioactive Effluents: Liquid PAGE 1 Liquid Releases JULY A GUST S NOVEMBER DECEMBER.

A. Gross Radioactivity (8-Y) QUARTER III QUARTER IV

1. Total Release (mCj ) 1 0 08 E+02 r 1 17 'E+02 5 98 EW2 2.46 E+03 1.25 E+03 1.79 E+02
6. 3 E-10 4. 8 E-10 2.3 E-09 7.6 E-09 6.3 E-09 5.3 E-09
2. Avg Concentration During Releases(yCi/ml) 4.9 E-10 4. 8 E-lo 2.3 E-09 7.6 E-09 5.6 E-09 8. 7 E-lo
3. Av Concentration for Month (uCi/ml) 8.1 E-08 5.4 E-09 7.0 E-09 2.6 E-"08 4.9 E-.08b 7.0 E-08c
4. tax Concentration Released (@CD/ml) ~
5. Percent of Technical Specification Limit for Total Activity Released (%)

1.65 E+01 7 '8 E+Ol B. Tritium

1. Total Release (Ci) 8. 14 E+01 5.64 E+Ol 1.26. E+02 1.03 E+02 8.75 E+01 5.61 E+01
2. Avg Concentration During Releases(yCi/ml) 4.8 E 07'.
2. 3 E-07 4. 7 E-07 3.2 E-07 4.4 E-07 1. 7 E-06 Av Concentration for Month (pCi/ml) 3.7 E-07 2. 3 E-07 4. 7 E-07 3.2 E-07 3.9 E-07 2.7 E-07 C. Dissolved Noble Gas
1. Total Release (mCi) 2.87 E+Ol, 5.39 E+01 1.55 E+Ol 4.16 E+Ol 6.67 EW1 4.69 E-Ol
2. Avg Concentration During Releases(pCi/ml) 1.7 E-10 2.2 E-10 5.8 E 11 1.3 E-10 3.4 E-10 1.4 E-ll 1.3 E-10 2.2 E-10 5. 8 E-11 1. 3 E'-10 3.0 E-10 2.3 E-12
3. Avg Concentration for Month (pCi/ml)

D. Gross Alpha Radioactivity

1. Total Release (mCi) (<4. 2 E-09) <4.2 E-09) (<7.5 E-09) (<9.4 E-09) (<1.1 E-08) 9.4 E-03
2. Avg Concentration During Releases(pCi/ml) (<2. 5 E-20) <1. 7 E-20) (<2.8. E-20) (<2.9 E-20) <5.6 E-20) 2. 8 E-13
3. A'vg Concentration for Month (pCi/ml) (<1.9 E-20) <1.7 E-20) (<2.8 E-20) (<2.9 E-20) (<4.9 E-20) 4.6 E-14; E. Volumes
1. Vol of Liquid Haste to Discharge (Liters) 9.45 E+06 6.87 E+06 7.31 E+06 1.35 E+07 1 08 F+
2. Vol of Dilution Water During Rel (Liters) 1.71 E+1] 2.46 E+ll 2.65 E+ll 3.24 E+11 1.97 E+ll 3.37 E+10
3. Vol of Dilution Water for Month (Liters) 2.22 E+ll 2.46 E+ll . 2.65 E+ll 3.24 E+ll 2.23 E+ll 2.06 E+ll NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

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Tabl e I Re ort of Radioactive Effluents: Li uid - Total PAGE 2 Isotope Unit JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Ag-llOm mCi 1.58 E+00 6.91 E-Ol 6.31 E-01: 1.68 E-Ol 2.30 E-Ol 3.59 E-ol Ba-139 mCi 3.12 E+00 Ba-140 mCi 4.49 E-01 . (<3.0 E-07) (<2.9 E-07) (<2.5 E-07) 1.21 E+00 2.07 E-01 Co-57 mCi 6.24 E-02 Co-58 mCi 2.00 EWl 3.58 E+00 1.'78 E&0 9.48 EWO 7.51 E+01 3.24 E+Ol Co-60 mCi 1.06 EWl 2. 7 EWO 8.46 E-01 3.10 E+00 7.22 F 0 Cr-51 mCi (<4.5 E-07) (<2. 4 E-07) .1.6 E+00 (<2.2'-07) 5.59 E-01 3.55 E-ol Cs-134 mCi, 7.54 E+00 1.15 E+00 3.02 E+00 1.28 E&0 7.75 E+00 2.37 E+Ol Cs-137 mCi 1.26 E+01 2.07 E&0 3.09 E+00 4.65 E+00 1.16 E&l 4.32 E+Ol Cs-138 mCi 4.56 E+Ol 1.37 /+02 2.78 E+Ol F-18 mCi 1.19 E+00 1.13 EW2 6.50 E+0 Fe-59 mCi 4.59 E-0 <'4.7 E-08 <3 1.14 EWO 7 8 F.

I-131 mCi 2.74 E+Ol 2.01 E&1 5.79 E+Ol 3.24 E+02 I-132 mCi 1.26 E+00 1.73 E+01 1.06 E+02 3.20 E+02 1.59 E+02 I-133 mCi 2.58 E+00 2.24 E+Ol 1.38 E+02 7.24 E+02 3.36 8+02 I-134 mCi 1.61 E+00 1.48 E+Ol 9.79 E+01 2.49 E+02 6.13 E&l I-135 mCi 7.78 E+00 1.27 E+02 5.33 E+02 2.46 E+02 La-140 mCi 2.87 E+00 2.0 E-01 (<7.7 E-09) . (<9. 4 E-09) (<1. 4 E-08) 3.65 E+00 Mn-54 mCi 6.09 E-01 .8.98 E-02 8.36 E-02 8.83 E-01 6.76 E-01 1.94 EWO Mo-.99/Tc-99m mCi 2.84 E+00 8.76 E-.01 Na-24 mCi 2.14 E+01 1.26 EW1 Nb-95 mCi (<4.1 E-08) 4.48 E-02 (<2.4 E-08 <1.5 E-08 <4. 7 E-08 7.90 E-01 RU-103 mCi (<4.9'-08) (<2.7 E-08} (<2.7 E-08) (<2. 2 E-08) (<7.4 E-08) 2.66. E-Ol Sb-124 mCi 3.54 E+00 1.07 E-01 2.05 E-Ol (<2. 8 E-08) 1.31 E+00 8.23 E-01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

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able I Re ort of Radioactive Effluents'. Li uid - Total isotope Unit JULY . AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Sb-125 mCi 2.09 E+00 (<8.1 E-08) 2.12 E-01'<6.6 E-08 3.98 E-01 Sr-89 9.0 E-ol 1.74 E-01 2.47 E-02 8. 4 E+00 7.20 EWO 8.31 E-01 Sr-90 mCi (<2.8 E-09) (<3.2 E-09) (<3.2 E-09 4.4 E-02 3 W-187 mCi (<l. 2 E-07) (<7. 7 E-08) 4.87 E-01 (<4. 8 E-08) (<l. 8 E-07) (<1.4 E-07)

Zr-95 mCi, (<6.6 E-08) <3.5 E-08 <3.2 E-08 <2 .-08 Unidentified mCi 1.23 E+01 2.38 E+0 1.24 8+01 0 EW TOTAL mCi 1.08 E+02 1.17 E+02 5.98 E+02 2.46 E+03 1.25 E&3. 1.79 E+02 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

T a bl e I Re ort o f Radi oaetive Effluents: Li uid - Paste..Dis osal S stem PAGE Isotope Unit JULY ~ AUGUST SEPTEMBER OCTOBER NOVEL $ ER DECEMBER Ag-110m mCi 1.58 E+00 6.91 E-Ol 6.31 E-01 1.68 E-01 2.30 E-01 3.59 E-01 Ba-140 mCi 4.49 E-01 (<3.0 E-07) E-07) '<2.9

(<2.5 E-07) 7.76 E-01 2.07 E-01 Co-58 1.80 E+Ol. 3.58 E+00 1.78 E+00 1.49 E+00 7.43- E+01 2.11 E+01 Co-60 mCi 6.12 EWO 1.25 E+00 8.05 E-01 4.68 E-O 4.14 E+00 2.72 E+00 Cr-51 mCi (<4.5 E-07) (<2. 4 E-07) (<2. 8 E-.07) (<2. 2 E-'07)'.15 5.59 E-01 3.55 E-ol Cs-134 mCi 7.09 E+00 1.15 E+00 1.75 E+00 E+00 9.4 E-ol 1.12 E+00 Cs-137 mCi 1.17 E+Ol 2.0 E+00 3.09 E&0 2.03 E&0 2.17 E+00 2.12 E+00 Fe-59 mCi 4.59 E-01 (<4.7 E-08) (<3.1 E-08) ,(<3. 3 E-08) 1.14 E+00 7.81 E-01 I-131 mCi 2.69 EW1 1.99 EWl 1.83 E+Ol 2.X2 E+Ol 4.81 EW1 2.77 E+01 I-133 mCi (<5.2. E-08) 3.44 E+00 1.53 E+00 2.18 E-01 (<7:8 E-08) (<5.7 E-08)

La-140 mCi 2.87 E+00 2.0 E-Ol (<7..7 E-09) (<9.4 E-09) .(<1.4 E-08) 2.9 E+OO

'<1.7 Mn 54 mCi 4.37 E-ol 8.98 E-02 8.36 E-02 E-08) 4.94 E-ol 2.02 E-01 Nb-95 mCi (<4.1 E-08) 4.48 E-02 (<2. 4 8-08) (<1.5 E-08) (<4. 7 E-08) 1.01 E-Ol Ru-103 (<4;9 E-08) (<2.7 E-08) (<2. 7 E-08) (<2.2 E-08) <7.4 E-08 1.05 E-0 Sb-124 mCi 3.54 EWO 1.07 E-Ol 2.05 E-Ol (<2. 8 E-08 1.31 8+00 Sb-125 mCi 2.09 E+00 (<8.1 E-08) 2.12 E-Ol (,<6 . 6 E-08) 3.98 E-01 2.55 E-01 Sr-89 mCi 5.02 E-01 1.62 E-Ol 2.47 E-02 3.36 E-01 <7.0 E-09 5.24 E-02 Sr-90 mCi (<2.8 E-09) (<3.2 E-09) (<3.2 E-09) . (<3.3 8-09) (<7.0 E-09) <3.1 E-09 W-187 mCi (<1.2 E-07) (<7.7 E-08) . 4.87 E-01 (<4. 8 E-08) (<l. 8 E-07) (<1.4 E-07)

Zr-95 mCi (<6.6 E-08) (<3;5 E-08) (<3. 2 E-08) (<2.9 E-08) (<8.7 E-08) E-02

'.72 TOTAL mCi 8.17 E+01 3;26 E+Ol 2.89 E+Ol 2.71 E+Ol 1.35 E+02 6.09 E+Ol NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

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Table X Report of Radioactive Effluents: Liquid Secondar S stem PAGE 5

'Isotope Unit JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Ba-139 mCi 3.12 E+00 Ba-140 'mCi 4.38 E-01 Co-57 E-02

'.24 mCi Co-58 mCi 2.04 EWO 7.99 E+00 8.2 E-Ol 1.13 E+Ol Co-60 mCi 4.52 E+00 1.45 E&0 4.11 E-02 2.63 E&0 3.08 MOO: 1.37 E+01 Cr-51 mCi 1.6 E+00 Cs-134 mCi- 4.50 E-01 1.27 E+00 1.31 E-01 6.81 E+00 2.26 E+Ol Cs-137 mCi 8.88 E-01 6.67 E-02 2.62 E&0 9.4 E&0 4.11 E+01 Cs-138 4.56 E+Ol 1.37 E+02 2.78 E&1 F-18 mCi . 1.19 E+00 l. 13,E+02 6:50 E+01 I-131 4.99 E-Ol 1.55 E-ol 3.96 EWl 3.03 E+02 1.64 EW2 1.58 E+Ol I-132 mCi 1.26 E+00 1.73 EWl 1.06 E+02 3.20 E+02 1.59 E+02 I-133 mCi 2.58 E+00 1.90 E+Ol 1.36 E+02 7.24 E+02 3.36 E+02 I-134 mCi 1;61 E+00 1.48 E+01 9.79 E+01 2.49 E+02 6.13 E+Ol I-135 mCi 7.78 E+00 1.27 E+02 5.33 E+02 2.46 E+02 La-140 mCi 7.46 E-01

~ Mn-54 mCi -1.72 E-01 8.83 E-01 1.82 E-Ol 1.74 E+00 Mo-99/Tc-99m mCi 2.84 E+00 8.76 E-01 Na-24 mCi 2.14 E+01 1.26 E+01 Nb-95 mCi 6.89 E-01 Ru-103 mCi 1.61 E-01 Sb-125 mCi 2.90 E-01 Sr-89 3.98 E-01 1.17 E-02 8. 1 FiKO 7.2 E+00 7.79 E-01 Sr-90 mCi (<2.8 E-09) (<2:8 E-09) 4.4 E-02 3.4 E-03 2.86 E-02 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

Table I Report of Radioactive Effluents: Liquid Secondary System PAGE 6 Isotope Unit JULY 'UGUST SEBTEMBER -

OCTOBER NOVEMBER DECEMBER Zr-95 mCi 6.86 E-02 Unidentified 1.23 E+01 2.38 E+Ol 1.24 Eml 1.07 E+01 1.59 E+01 9.44 E&0 TOTAL mCi 2.67 E+Ol 8.44 E+01 5.69 E+02 2.44 E+03 1.12 E+03 F NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

I Table I Report Of Radioactive Effluentd: Liquid -Dissolved Gas PAGE 7 Total JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Kr-85 2. 72 E+01 . (<7.9 E-06) (<7. 2 E-06) (<3. 7 E-06) 2.56 E+01 ~

(<6. 7 E-06)

Xe-133 mCi 1.48 EWO 4.90 E+Ol .1.08 E+01 1.84 2+0'1 2.31 E+Ol 4.6 Xe-133m mCi (<3.7 E-07) 2:54 E+00 <2.8 E-07 <2.4 F.

Xe-135 mCi (<4. 1 E-08) 2.37 E+00 4.71 E+00 2.32 E+01 1. 8 E&1 (<2. 1 E-08)

Waste Disposal System Kr-85 2.72 EW1 (<7.9 E-06) (<7.2 E-'06) (< 3. 7 P-06) 2'.56 E&1 (< 6. 7 E-06 Xe-133 mCi 1.48 EWO 4.90 EW1 7.02 E+00 5.49 E&0 1.33 F+0 Xe-133m mCi (< 3. 7 E-07) 2.54 E+00 (<2.8 E-07) <1.7 E-07 <2.4 E-Xe-135 mCi (<4.1 E-08) 2.37 E+00 2.73 E-ol 1.76 E-ol (< 2. 6 E-07) (< 2. 1 E-08)

Secondar S stem Xe-133 mCi 3.79 E+00 1.29 E+Ol 9.8 E+00 Xe-135 mCi 4.44 E+00 2.31 E+01 1.8 ~

E+01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

Airborne Releases Airborne releases to the atmosphere occurred from release of gas decay tanks, via the instrument bleedline, containment purges, and from the secondary system during conditions of primary to secondary leakage.

The techniques employed in determining the radioactivity in airborne releases are:

a)'amma spectrum analysis for fission and activation gases.

b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89-90 determination, gross alpha analysis, and gross beta-gamma analysis.

c), Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Condensation of water vapor in a gas.sample followed by analysis for tritium using liquid scintillation techniques.

All sporadic gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 equivalent by use of the plant vent process monitor recorder chart.

The maximum rated capacity for the hogging jets and the maximum measured flowrate for the condenser air ejectors, and an estimate of the t

rate of exhaust from the atmospheric dumps were used to conservatively estimate. the airborne releases from the secondary system whenever applicable.

The- following comments will aid in the interpretation and evaluation of the airborne release data presented in Table XX.

1. Calculation of total radioactivity of noble gases, I-131, and particulates is based upon detectable radionuclides only.
2. The applicable limit for release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calendar quarter.

The percent of the applicable limit for total gaseous release was computed as follows:

Total curies released in

/ f Li it aseous waste durin uarter x 100%

(.012 Ci/sec) (seconds in quarter)

3. The applicable limi,t for the release of I-131 and particulate radio-nuclides with half-lives greater than eight days in airborne waste is:

E 'ec'

"i MPCi

< 10,000 m

3

, where Q. =

Ci/sec i

release rate of .th nuclide, and MPC i = maximum ~<grmissible of the i nuclide.

concentration The release rate, Q , was determined by dividing the total activity released in Ci, for the ith nuclide (tl/2 > Sd), during the calendar

'I quarter by the seconds in the quarter.

MPCi values were obtained from Appendix B, Table II, Column 1, 10 CFR 20. The MPC chosen was the most conservative value of either the soluble or insoluble MPC for each isotope.

The percent of the applicable limit was determined as follows:

x 100%

MPCi

% of Limit = 3 10,000 m /sec

4. The,,maximum. gaseous release ate forqach month is listed in Table II, page 1, under section A, line 3. The applicable limit for maximum allowable release rate is 6.7 EW4 gi/sec.
5. All values reported in Table II, page 2, include the particulate .

'activity released from both the gas waste disposal system and the secondary system during conditions of primary to secondary system leakage. If a minimum detectable activity value was not calculated for an isotope; it will be listed as ( ).

6. All values for gaseous radionuclides and halogens reported in Table II, page 3, include the quantity of gaseous nuclides and halogens re-leased via the waste disposal system and secondary system.

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Table II Report of gadioactive Effluents: Airborne Particulate PAGE 2 Isotope Unit JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Ag-110m Ci (<1.4 E-13) (<5.3 E-14) (<3.3 E-14) ~

2.4 E-05 (<4.2 E-14) (<5.6 E-13)

Ba-140 Ci 1.3 E-05 (<3.1 E-13) (<4.9 E-13) 9.7 E-06 2.4 E-05 (<3.6 E-12)

Ce-141 (<6.8 E-14) ~ (<2.2 E-14) (<2.5 E-14) (<1.6 E-13) <3.1 E-14 1.1 E-04 Ce-144 Ci- (<3. 0 E-1.3) '(<l.l E-13) (<l. 1 E-13) (<6. 8 E-13) (<1.4 E-13) 6.6 E-05 Co-57 2. 7 E-06 (<1.2 E-14) (<1.3 E-14) 1.0 E-05 (<1.9 E-14) 2.4 E-05 Co-58 9.0 E-04 4. 3 E-05 2.0 E-05 8. 8 E-03 4.9 E-.04 4.8 E-03 Co-60 Ci 1.0 E-03 1.8 E-04 1.8 E-04 1.6 E-03 1.2 E-04 4.6 E-03 Cr-51 Ci (<8.5 E-13) (<2.1 E-13) (<2.4 E-13) 8.0 E-04 <4.1 E-13 3.9 E-04 Cs-134 Ci 2.4 E-05 1.0 E-05 3.5 E-05 9. 1 '-06 Cs-136 Ci (<7.7 '-14) (<3.3 E-14) 1.0 E-05 (<1.4 0-13) (<4. 2 E-14) (<3.5 E-13)

Cs-137 Ci 4.8 E-05 5. 2 E-05 6.0 E-05 2.0 E-05 fj.2 E-05 8.4 E-06 Fe-59 Ci (<2.1 =E-13) (<6. 3 E-14) (<5.0 E-14) 4.1 E-05 (<6.6 E-14) 6.7 E-05 I-131 1. 7 E-.'5 2.2 E-05 4.5 ~ E-05 2.3 E-05 4.8 E-05 8.4 E-06 La-140 1. 2 E-05 (<3. 3 E-14) 9.5 E-06 8.0 E-06 1.6 E-05 (<1.8 E-13)

'n-54 Ci 3.6 E-05 5.2 E-06 2.1 E-06 9.7 E-05 5.5 E-06 2.0 E-04 Nb-95 Ru-103 f

'i Ci 9.3

(<1. 1 E-06 E-13)

(<3.0

(<2.5 E-14)

E-14)

(<2. 4

(<2.9 E-14)

E-14) 8.3

'<2.5 E-05 E-13)

(<4.5

(<5.0 E-14)

E-14) 3.8 4.,2

~ E-04 E-04 Sb-124 Ci <l. 7 E-13} (<3.9 E-14) (<3. 3 E-14) 1.0 E-04 (<6.0 E-14) (<3.8 E-13)

Sr-89 Ci 6.8 E-06 1.6 E-06 3.5 E-06 2.8 E-06 6 E-Sr-90 Ci <1.0 E-06) (<7.5 E-07) 9.4 E-08 3.3 E-07 (<9.0 E-07) 6.9 E-07 Zr-95 Ci < 1. 7 E-13) (<5. 1 E-14) (<4. 3 E-14) 4.3 E-05 (< 7.0 E-14) 2.2 E-04 TOTAL Ci 2.07 E-03 3.14 E-04 3.65 E-04 1.17 E-02 7.72 E-04 1.13 E-02 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/cc.

gl, able II Re ort of Radioactive Effluents: Ai born G Fission and Activation Gases JULY AUGUST , SEPTEMBER OCTOBER NOVEMBER DECEMBER Isotope Unit Ar-41 Ci -2.65 E+OO 1.58 EWl 1.46 Ef00 3.95 EWO Kr-85 Ci (<3.8 E-05) 1.86 E-01 5.85 E-02 3.18 E-01 1.84 E+00 2. F-Kr-85m Ci 1.06 E-01 7.7 E-01 1.42 E&0 1.33 E+Ol 7.36 E+00 2.36 E-O Kr-87 Ci (<2. 4 E-07) 1.01 E-Ol 2.02 EWO 1.57 E+Ol 1.27 E+Ol <1.4 E-06 Kr-88 Ci 1.39 E-01 4.38 E-01 1.98 E+00 1.76 E+Ol 1.05 E+01 (<3.7 E-06)

Xe-131m Ci (<4.9 E-06) 3.8 E (<9.6 E-05) 9.77 E-02 1.02 E-01 1.68 E-Ol Xe-133 Ci 1.18 E+03 1.39 E+03 1.42 E+03 2.35 E+03 . 2.36 E+03 4.85 EW2 Xe-133m Ci 3.98 E-01 2.1 E+00 '.56 E-01 5.12 E+00 6.90 E-01 3.18 E+00 Xe-135 Ci 1.71 E+00 9.59 E+00 1.05 E+Ol 1.05 E+02 5.92 EW1 4.70 E+00 Xe-135m Ci 8.45 E-ol 1.61 E&0 8.27 E&0 4.65 E+01 1.02 E+02 (<6.9 E-07)

Xe-138 Ci (<2.5 E-07) (<4.6 E-06) 3.96 E+00 2.32 E+Ol 3.94 E+01 (<4.5 E-06)

TOTAL Ci. 1.19 E+03 1.42 E+03 1.45 E+03 2.59 E+03 2.60 E+03 5 I ~

Halogens (gaseous) JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER

'soto e Unit

I-131 Ci 3.3 E-02 3.8 E-02 2.5 E-02 6.0 E-02 6.88 E-02 7 E I-133 Ci E-03

'.7 3.7 E-02 l. 2 E-02 5.0 E-02 1.9 E-02 7. 3 E-03 I-135 Ci '(< l. 3 E-13) 8.0 E-03 7.0 E-03 2.8 E-02 1.'3 E-02 (< 2. 1 E-13)

Br-82 Ci 5.8 E-04 7.8 E-04 TOTAL 4.17 E-02 8.36 E-02 4.40 E-02 1.39 E-01 1.01 E-01 8.28 E-02 NOTE: Numbers in parentheses represent maximum sensitivity in p"Ci/cc.

RADZOACTIVE WASTE July 1, 1977 to December 31, 1977 Packed Ci Cu. Ft.

Total 252.781 18,267.30 On site as of January 1, 1977 37.707 1,409.85 Dates of Shipment and Disposition 1 July, 1977 Buried in Barnwell, South Carolina 8 July, 1977 8 July, 1977 8 July, 1977 9 July, 1977 12 July, 1977 12 July, 1977 13 July, 1977 17 July, 1977 20 July, 1977 28 July, 1977 ll August, 22 August, 1977 1977 25 August, 1977 30 August, 1977 31 August, 1977 September, 1977 September, 1977 9 September, 1977 12 September, 1977 13 September, 1977 14 September, 1977 23 September, 1977 29 September, 1977 3 October, 1977 5 October, 1977 7 October, 1977 17 October, 1977 4 November, 1977 7 November,, 1977 9 November, 1977 10 November, 1977 3 December, 1977 3 December, 1977 5 December, 1977 8 December, 1977 10 December, 1977 16 December, 1977 19 December, 1977 21 December, 1977 22 December, 1977 28 December, 1977 Total Shipments 42 TURKEY POINT: Units 3 g 4 En'vi;r'o'nmenta'1a'd'i'olo 'ica'1 Mon'itor'in (7-01-77 to 12-31-77)

1. Introduction This report is submitted in accordance with Turkey Point Plant Technical Specifications.

All environmental samples were collected and analyzed in accordance with the requirements of the Technical Specifi-cations. The minimum frequency of collection and analyses for specific radionuclides and sample types as required by these specifications has been met or exceeded.

No harmful effects or evidence of irreversible damage to the environment or to the health and safety of population

'groups in the Turkey Point Plant area have been detected by this monitoring program.

2. The Monitorin Pro ram

~y,>>

Period Covered: This current report covers the period from b

Anal tical Res onsibilit : Environmental radiological mons.torxng at ur ey oint Plant is carried out by the Orlando Radiological Laboratory of the Department of Health and Rehabilitation Services of Florida (DHRS) . All samples are collected and analyzed by DHRS personnel.

Number of Sam les Anal zed: A total of 700 analyses on samp es co ecte rom 3 different sampling locations were performed during the period. of this report. TABLE 1 summarizes the mean and range values of these analyses.

S lit-Sam le Anal ses: At least 12 samples were collected to e ana yze y t e DHRS/ERDA Split-Sampling Program.

3. Evaluation of Data As noted in TABLE 1, some of the sampling locations in PTP's environmental radiological monitoring programs showed evidence.

of having concentrations of a particular radionuclide in a specific material much higher than the'bserved mean for all sampling locations where the same type of sample material was collected and analyzed for that particular radionuclide.

Except for, the conclusions that follow, these data are more

representative of background variations resulting from the Chinese weapon tests of 1977, a) The H concentration at sampling location T-97 is consistent with H levels previously observed in the Cooling Canal System.

b) No significant increases above previously reported data have been observed in GB-DS and 3

H concentrations at location T-75 in the Fresh Water Canals.

c) The H concentrations in the Ground. Water Wells at sampling T-88, T-91, and T-92 continue to be of the same magnitude as previously reported.

d) A slight increase in the concentration levels of 60 Co, 95 Zr, Cs and Ce have been noted in the bottom sediments of the Cooling Canal (at T-84). This increase seems consistent with the general environmental BG increase from Chinese weapon test fallouts.

e) The assay of estaurine sediment samples (especially at locations T-66 and T-94), manatee grass (at locations T-59 and T-69), sponges (at T-59, T-69, T-86, T-93, and T-94), mangrove leaves (at T-51, T-58, T-72, and T-86) and soils (at T-SZ, T-57, T-S5, T-56, and T-58) reflect that the observed radionuclide concentrations are attributable to fallout.

Trend plotting of air particulate and direct radiation data, especially in those periods when fallout occurrences have been observed, reveal no plant-related variations.

All data have been evaluated with respect to pre-operational data and have been found to be within the +Zq limits observed

for these pre-operational data, Comparisons of sample location data with that of the'rogr'am,'s control sample location are also given in TABLE 1,

4. Conclusions The concentration level of any radionuclide reported in TABLE 1 will contribute much less than the maximum permiss-ible limits of individual or population group intake that could result if there had been a continuous exposure to radionuclides having concentration values equal to those permitted by APPENDIX B, TABLE II, 10CFR20. Therefore, the operations of Turkey Point Plant Units 3 P 4 are not contributing harmful effects or irreversible damage to either the environment or to the health and safety to individual or population groups in the regions surrounding Turkey Point Plant.

22-

TABLE 1 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAH SSNARY NAME OF FACILITY Turke Point DOCKET 50. 50-250 -251 LOCATION OF FACILITY Dade Count Florida REPORTING PERIOD 7-01-77 to 12-31-77 All Indicator Location with Hi hest Iiean Control Number of Nonroutine Itndium or Pathway Analysis Number of Locations Sample Location Location Reported Sampled Uni t for Sites Samples Analyses Wean Range Distance and Direction Iiean Range Wean Range Measurements

1. AIR FILTERS 1.1 Air Particu- Ci/ms GB 214 214 0.19 0.02- T-51: Homestead Bayfront 0.25 .02- 0.19 0.03- None b

Tatea 4.12 Park; NNW, 2 miles 4.12 2.06 T-52: Florida City Sub- 0.20 .02-station. W 8 miles 3.10 T-58: On-Site Entrance 0.22 .02-RoOa  ; MNW, 1 mile 3.43 T-71: Girl Scout Camp, 0.23 .02-on site 3.69 1.1A Air Iodines 'i/ms 1 slI 214 214 ND (d) None ND None 1.2 Direct Radia- Rem/h 132 132 5.2 3 0-(b) T-52: Florida City Sub- $ ,4 .0-6.0 6.0 4.0-7.0 None

~ton station; W, 8 miles T-56: Princeton Substa- 5.8 .0-7.0 t1On (SW 248 St); MNM, 2.5 miles T-58: On-Site Entrance 5.5 .0-8.0 Road; MNM, 1 mile T-64: Natoma Substation; 6.0 .0-7.0 ZAE, 30 miles T-78: COB Headquarters, 5.3 .0-7.0

%anger House; on site T-79: Guardhouse; on sit 5.7 .0-8.0

0 All Indicator Location with Ki hest Wean Control Number of Nonroutine Analysis Number of Locations Sample Location Location~ ~

Reported Hedium or Pathway Samoled Unit for Sites Samples Analyses Wean Range Distance and Direction liean Range Wean Range Measurements 1.3 ~Prect ftat1on pCi/it GB-DS 8.2 ND-28 T-64: Hatoma Substation; 12.0 4-28 12.0 4-28 None EHE, 30 miles GB-VDS 0.9 HD-28 T-57: Dolan's Farm; WNW, 1.0 ND-3 2.0 ND-8 ZS miles T-64: Natoma Substation; 2.0 ND-8

~EN , 30 miles Gama ND None ND

'scan sH <200 None <200 WATER

.1.1 Estaur ine pCi/t sH 10 10 10 225 200-800 T-93: Pelican Bank, Card 450 200- None Round; E, 1.7 miles 800 4'Sr 10 10 10 ND Hone SOSr 10 10 10 ND None

.1.2 Cool in Canal pC1/it 5117 200-6700 T-97: Loch Rosetta; on 5150 3300- None site 6700 4$

Sr ND Hone

'4sr 6 0.5 ND-1,4 Hone

Location with Hi hest tiean Control Number of All Indicator Nonroutine Number of Locations Sample Location t.ocation~ ~

Vedium or Pathway Analysis Reported Sampled Unit for Sites ,Samples Analyses tlean Range Distance and Direction Wean Range Wean Range Measurements 2.1.3 Fresh Water pC1/tt, GB-DS 142 ND-390 T-75: Florida City; 279 120-39 Hone

~ana s dna ; NNW, 1.5 miles GB-UDS Hone sll 357 <200-1000 T-75: Florida City Canal; 513 170-8%, 1.5 miles 1000 2:2 Potable Water pCl/a GB-DS 4-14 T-57: Dolan'.s Farm; WNW, 10,5 7-14 None

~sa> s miles GB-UDS ND tlone r

<200 None 2.3 Ground Water pCi/i sH 12 12 900 <200-f400 T-88: Mell E-14 1300 900- Hone ttaas 1700 T-91: Mell G-10A 1300 700- tlone 1900 T-92: Mell G-24A 2150 2100-2400 09Sr 12 12 Hone 90Sr 6 12 12 Hone

Location with Hi hest Hean Control Number of All Indicator Nonroutine Analysis Number of Locations Sample Location Location Reported Fedium or Pathway Sampled Uni t for Sites Samples Analyses Hean Range Distance and Direction Wean Range Nean Range aHeaSureotentS

3. BOTTOH..SEDI-.

HEHTE=

3.1 ~Cool an Canal pCi/kg "7Cs 63 HD-140 T-84: Discharge Canal; 100 60-140 None south side of bridge 9 SZr 335 100-700 T-84: Discharge Canal; 525 390-700 south side of bridge 49Sr Hone 94Sr HD Hone 1133Ce 550 200-1000 T-84: Discharge Canal; 800 600-

~sout side of bridge 1000 44Co 155 100-230 T-84: Discharge Canal; 170 110-230 south side of bridge

.2 Estaurine pCi/kg '"Ce 86 D-340 T-66: Card Sound, North 260 210-310 None

'oOOauseway T-94: Pumpkin Key, Card 290 40-340 Sound; SSE, 8 miles 9SZr 134 D-420 T-66: Card Sound,'North 150 130-170 of useway T-94: Pumpkin Key 390 360-420 "Sr ND Hqne

Location with Hi hest Mean Control IHumber of All indicator Nonroutine Hedium or Pathway Analysis Number of Locations Sample Location Location Reported Sampled Unit for Sites Samples Analyses Hean Range Distance and Direction Bean Range Hean Range Heasurements 905r ND Hone

4. AIINTIC BIOTA

.1 Crustacea pCi/kg 9Szr 36 ND-170 T-59: Elliott Key; E, 9 g0(e) 0-120 None

~mles T-66: Card Sound; North 70(f) 0-100 onnauseway .

09Sr Hone 90Sr ND Hone .

.2.A Fish Carni- 09Sr ND None Hone vore 90Sr ND. None

.2.8 Fish Herbi- 09Sr ND Hone None vore 90Sr 5 ND-27 T-59: Elliott Key; E, 9 23(g) 19-27 mlles

~ 3.A Hanatee Grass 9 52r 648 90-1300 T-59: Elliott Key; E, 9 1200 100- None m es 1300 T-69: Elliott Key; south 870 20-920

=

end

Location with Hi hest Yean Control Number of All Indicator Nonroutine Number of Locations Sample Location Location Nedium or Pathway Analysis Reported Sampled Unit for Sites Samples Analyses Nean Range Distance and Direction Iiean Range Wean Range Neasurements 49Sr ND None

'4Sr ND None 4.3.B ~Son es pCi/kg '4Co 42 ND-170 T-94: Pumpkin Key, Card '50 130-170 Hone Sound; SSE, 8 miles 146RU 6 225 ND-1700 T-93: Pelican Bank, Card 1300 00-Sound; E, 1.7 miles 1700 9$ Zr 1170 200-5400 T-93: Pelican Bank, Card 5200 000-Sound; E, 1.7 miles 5400 1llCe 1336 00-2100 T-59: Elliott Key; E, 9 2000 1900-

~mles 2100 T-69: Elliott Key; south 1700 600-end 1800 T-86: West Arsenicker Key 1900 1800-ard Sound 2000 .

T-93: Pelican Bank, Card 1700 400-ound; E, 1.7 miles 2000 TERRESTRIAL BIOTA pCi/kg 1$ 7Cs 280-300 None None I ~

~ \

Location, with Hi hest Mean Control Humber of All indicator Nonroutine Number of Locations Sample Location Location>> ~

ltedium or Pathway Analysis Reported Samoled Unit for Sites Samples Analyses t<ean Range Distance and Direction Mean Range Mean Range Measurements 89Sr ND Hone soS ND None 5.2.2 ~Food Ceo

~ ~

pCi/kg ~~Sr None None

'4Sr 37 17-57 Hone 5.2.3 Man rove pCi/kg ~sZr 513 30-1000 T-51: Homestead Bayfront 630 60-700 350 320-380 None eaves Paar  ; tiHW, 2 miles T-86: West Arsenicker Key 900 0-Card Sound 1000 435 D-1300 T-51: Homestead Bayfront 700 00-900 HD r ar; NNW, 2 miles T-72: Boy Scout Camp; on 900 00-s te 1200

-86: West Arsenicker Key 1000 00-ard Sound 1300 osSr 35 HD-1 25 -51: Homestead Bayfront 40 20-60 ND ar ; NNW, 2 miles

-72: Boy Scout Camp; on 100 2-125 te

-86: West Arsenicker Key 70 50-90 rd Sound

I I

8 Location with Hi hest Mean Control Number of All indicator Nonroutine Analysis Number of Locations Sample Location Location Reported Medium or Pathway Sampled Unit for Sites Samples Analyses Mean Range Distance and Direction iiean Range Mean. Range Measurements 905r 7 7 12.3 6-26 T-51: Homestead Bayfront; 22 18-26 9-13 NNW, 2 miles T-58: On-Site Entrance 20 18-22 Kaa; WNW, 1 mile

'46Ru 244 ND-1000 T-86: West Arsenicker Key, 700 400-Card Sound 1000

.3 Soil pCi/kg xsvCs 333 60-780 T-55: Silver Palm Drive 530 00-560 80 60-100 None gQ 232 St)

T-56: Princeton Substa- 730 80-780

~t on; WNW, 2.5 miles T-57: Dolan's Farm; WNW, 360 320-400 Z3 miles 9$ zr 776 100-2600 T-57: Dolan's Farm; WNW, 2500 2400- 340 300-380 AHQ, 4.5 miles 2600 T-5'8: On-Site Entrance 1000 30-Foaa 1070 1%6Ce 440 D-1400 T-57: Dolan's Farm; WNW, 1300 1200- 270 210-330 Z3 miles 1400 166Ru 114 D-900 T-57: Dolan's Farm; WNW, 700 500-900 ND C5 miles 695r ND None ND

J l

j

Location with Hi hest Mean Control Number of All Indicator ) Nonroutine Number of Locations Sample Location Location(

Medium or Pathway Analysis Reported Samoled Unit for Sites Samples Analyses than Range Distance and Direction Mean Range Mean Range Measurements

$ 05r 79 ND-480 T-52: Florida City Sub- 120 70-170 ND station; W, 8 miles T-57: Dolan's Farm; WNW, 420 360-480

~4. miles (a) T-54: Natoma Substation Hiami, ENE, 30 m les (b) All d at ese locati ns affe ted by fa lout patte s from ate Septe er Chinese bomb tests.

(c) ND ~ n-dete table 131 (d) Indi vi ual 1 ations wer all no -detectab e; however followi g weekly omposites showed detecta 10-0 -77 0. 140.01 Ci/m 10-1 -77 0, 5+0.02 Ci/m 11-0 -77 0. 7%.02 Ci/m (e) Lobste (f) Crab (g) Hull e (h) Racoon (I ) Ha lang

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Attached is a corrected copy of page 1 of the Airborne Section-of the Radioactive Effluent Release portion of the semi.-annual operating report for January through June 1977. Please replace your page 1 vith the attached copy.

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I II

4 TURKEY POINT PLANT UNITS 3 AND 0

. SEHIANNUAL OPERATING REPORT OF RADIOACTIVE EFFLUENT RELEASES AND ENVI RONNENTAL RAD I OLOG I CAL NON ITORI NG

'OR PERIOD JULY 1, 1976, THROUGH DECEi'1BER 31, 1976 IN CONPLIANCE k'IITH TECHNICAL SPECIFICATION 6,9,0

~ ~

f r

F TS TABLE OF CONTENTS s s a ~ s s s s s s ~ s ~ a ~ s ~ s 3.

INTRODUCTION s s s . s . . . 2 (A) RADIOACTIVE EFFLUENT RELEASES s s a ~ ~ ~ ~ s s ~ s a a 3 (1) LIQUID RELEASES ...,...,... 3 (2) AIRBORNE RELEASES . ., 33

~,

s s s s (3) SOLID WASTE BUR IAL s ~ ~ 3.9 (B) RADIOLOGICAL ENVIRONMENTAL MON I TOR I NG s ~ ~ ~ ~ s ~ ~ a a 21

r I THIS REPORT IS SUBMITTED IN ACCORDANCE WITH TURKEY POINT PLANT TECHNICAL SPECIFICATION SECTION 6)9iO, THIS REPORT COVERS THE DATA NECESSARY TO MEET THE SEMI-ANNUAL REPORTING REQUIREMENTS FOR (A) RADIOACTIVE EFFLUENT RELEASES AND (B) ENVIRONMENTAL RADIOLOGICAL t'10NI TORING s FOR THE PERIOD OF JULY 1, 1976, THROUGH DECEMBER 31, 1976.

1J y I li

1 Radioactive Effluent Releases A11 1'quid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Safety Guide 21 has been met or exceeded.

Li uid Releases Aliquots of reoresentative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2m gas flow proportional counter. The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases. Prequent periodic sampling and analysis were used to conservativel'y estimate the quantity of radioactivity released via the steam generator blowdown system.

The following comments will aid in the interpretation and evaluation

)

of the liquid release data presented in Table J

I, pages 1 through 7:

1. The reported values in Table I, page 1, include in their computation the quantity of radioactivity released from both the waste disposal system and the secondary system. 'he secondary system releases occurred when contaminated water was blown down from "the steam generators during primary to secondary leakage conditions, or when the generators were drained for repair or refueling.

~ ~

'I ~

1 I

2. The reported values in Table I, pages 2 and 3 are the total quantities.

of radioactivity for individual nuclides released from the waste disposal system and the secondary system together. The values in Table I, page 4 are for the waste disposal system only and pages 5 and 6 are for the secondary system only. During primary to secondary leakage, release of several short-lived nuclides occurred from the secondary system. These short-lived nuclides are not generally detected in batch releases from the waste disposal system due to the long holdup time of processed water.

3. Only those isotopes that were detected in the secondary system releases were reported. All non-detectable isotopes are listed as

( ) ~

4. Meekly and monthly composite samples for- the waste disposal system were prepared to give a proportional weight to each liquid release made during the designated period of accumulation. The composites were analyzed for gamma emitting isotopes on a multichannel analyzer attached to a high resolution Ge(Li) detector, and for Sr-89 and Sr-90, using a chemical separation and subsequent beta determination with a 2m gas flow proportional counter. Tritium was determined by I

use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2m gas flow proportional counter. A11.

concentrations for radioactivity determined from analysis of a composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing periods

I I

5. At least one representative batch of liquid effluent from the waste disposal system was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotopic concentrations were multiplied by the total volume released for the month in order to estimate the total dissolved gases released.

If more than one batch of effluent was analyzed, the concentrations are weighted in an appropriate manner. The results are totaled on a monthly basis in Table I, page 7. Dissolved gases from secondary system releases were determined from the samples of the individual releases. Isotopic concentrations were multiplied by the volume released to determine the quantity of radiogas nuclides released.

6. Pepresentative samples of secondary system batch releases were analyzed individually for gamma emitting isotopes and by analysis of a representative composite for tritium, gross alpha and selected beta emitters.
7. The applicable limit for release of radioactive material in liquid waste is five curies per quarter.
8. The following notes have been added to help explain some of the results in Table I which have been superscripted with a lower case letter:

Suoerscri t Notes The Q/MPC for this release was 0.071.

The Q/ifPC for this release was 0.69.

The Q/HPC for this release was 0.082.

Ho primary to secondary leakage was occurring; therefore, most short-lived isotopes were not present.

J Table I Report of Radioactive Effluents: Liquid Page 1 Liquid Releases July August September 'ctober November December A. Gross Radioactivity (8-y) Orrar er TT

l. Total Release (mCi 1.78 E+01 6.73 H+02 82 + 2.70 H+n2 6.n5 + 6.84 E+Ol
2. Avg Concentration During Releases(pCi/ml) 6.2 H-10 8.5 H-09 1.6 E-OS 9. 8 E-10 6.0 H-10 5. 1 F.-10
3. Av Concentration for Honth (pCi/ml) 5.9 E-11 2.4 H-09 1.6 E-08 9 8 E 10 4 4 E 10 3. 5 E-10
4. 1fax Concentration Releaserl (pCi/ml) 3.2 H-09 9.4 E-08a 4.2 F-07b 5.2 H-O 2.4 E-08 5.8 E-09
5. Percent of Technical Specification Limit for Total Activit Released  %) 9.02 E+01 8.0 '+00 B. Tritium
1. Total Release (Ci) ~

5.2 P+Ol 8.96 E+Ol 9.29 E+Ol 7.08 E+Ol 3.14 E+01 1.54 E+Ol.

2. Avg Concentration During Releases(pCi/ml) 1.8 E-06 8.6 E-07 3. 8 E-07 2.6 E-07 3. 1 E-07 Av Concentration for Honth (pCi/ml) 1.7 E-07 3.1 E-07 3.8 E-07. 2.6 E-07 2.3 E-07 C. Dissolved Noble Gas
1. Total Release (mCi) 1.7 H-Ol . 6.37 E+Ol 4.33 H+02 2.S7 E+01 2.62 E+02 (<5.1 E-06)
2. Avg Concentration During Releases(pCi/ml) 5.9 E-12 6.2 . E=10 1.8 H-A9 1.0 E-10 2,6 E-09 (<3.8 E-17)
3. Avg Concentration for Honth (rrCi/ml) 5. 7 H-13 2. 3 E-10 1. 8 F.-09 l. 0 F.-10 1.9 H-09 <2.6 H-17 D. Gross Alfrha Radioactivity
1. Total Release <3.0 E-09 <7.3 E-09 2.4 E-02 <4.2 F.-OS <4.2 H-08 <1.1 P.- 8
2. Av Concentration Durin Releases(pCi/ml) (<1.0 H-19 (<7.0 E-20) 9'. 8 E-14 (<1.5 E-19 (<4.2 H-19 (<8. 3 E-20)
3. Av Concentration for Honth (pCi/rnl) <1.0 E-20 <2.6 E-20 9.8 E-14 <1.5 H-19 <3. 1 P.-19 <5. t H-'20)

E. Volumes

l. Vol of Liquid Waste to Discharge (Liters) 1.34 H+06 5.85 E+06 1.54 E+07 1. 5 8+07 7.54 H+06 6.49 E+06 2, Vol of Dilution Water During Rel (Liters) 2.89 E+10 1.04 E+ll 2.46 E+11 2.76 E+11 1.01 E+ll 1.33 E+ll
3. Vol of Dilution Water for Honth'Liters) 3.0 H+ll 2.85 E+11 2.46 H+ll 2.76 H+11 1.36 E+ll 1.98 E+11 NOTE: Numbers in narentheses represent max.fmum sensitivity in pCi/ml.

~'

Table I Report af Radioac tive Effluents: Liquid Total Page 2 Isotope Unit July" . August September 'ctober November." December Ag-llom mCi 2.1 H-ol 4.5 E-01 3.0 E-ol aa-140 mCi (<2. 0 E-07) 4.92 P+00 (<1.9 H-07) (<2.7 E-07 <t . 5 r'-07 <3.9 H-O7 Ce-144 mCi (<1.1 E-O7) (<1.4 r;-O7) (<9.0 E-O8) (<1.4 E-07) (<2.3 H-O7) <1.8 F.-oj Co-58 mCi 1.1 F+00 1.3 F+00 1.18 E+02 1.09 E+Ol 9.83 H+00 3.04 E+01 Co-6n mCi 2.6 E-Ol 1.36 H+Ol 2.4 E+Ol 1.74 r+00 4.19 E+00 9.15 E+00 Cr-51 <1.7 E-O7 (<2.2 H-O7) 6.01 E+01 <2. 2 H-07 <..6 H-O +0 Cs-134 mCi (<2.6 . E-08) 7.25 H+00 2.54 E+02 1.31 E+01 1.22 E+00 3.84 E+00 Cs-136 mCi <1.5 E-08 8.7 E-ol 7.32 F+Ol 9 8 P-n n Cs-137 mCi (<2. 9 E-O8) 1.11 E+Ol 2.43 E+02 l. 4 H+Ol 3.1 H+00 5.83 E+00 Cs-138 mCi. 4.26 E+01 5. 69 E+Ol 7.1 E+00 P-18 mCi 1.59 E+Ol 1.37 E+02 3.17 E+01 FQ-59 mCi (<3.0 H-08) <8.7 E-n8) (<3.5 E-08) (<3.7 E-o&) (<6.0 E-08 <5.4 E-08 I-131 mCi 2.8 E-01 7.24 E+Ol 1.46 E+03 7.63 E+Ol 1.75 E+01 6.42 E-Ol I-132 mCi 7;95 E+Ol 8.05 E+01 8.5 E+00 4.9 E+00 I-133 1.67 E+02 8.67 E+02 4.62 E+Ol 5.53 E+00 I-134 mCi 8.85 P+Ol 1.66 E+01 4.2 F+00 5.4 r.-ol I-135 mCi 1.44 E+02 2.17 E+02 1.04 E+01 La-140 mCi (<1.1 E-08) 2.42 E+00 7.2 E-ol 7.6 E-02 (<3.0 E-08 <1. 6 E-08

2. 7 F.-02 7.2 E-Ol 4.87 H+01 .0 +

Ho-99 mCi 8.5 E-ol 2.16 E+00 1.9 E+00 Na-24 mCi 4.1 E+00 7.95 E+Ol 2.04 F+Ol Nb-95 mCi (<1.7 E-08 5.1 E-02 1.93 E+Ol 6.0 E-ol 1. 5 F.-ol 1.93 H+00 Sb-124 mCi 8. I E-01 E+00 3.3 H-Ol .. 4 .+OO +n Sb-125 mCi 3.0 E-Ol 9.2 2.3 E-ol 1.9 E+00 3.13 E+00 2.54 E+00 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

Table I Report of Radioactive Effluents: Liquids Total (cont) Page 3 Isotope Unit July - August September October November December Sr-89 mCi 3.2 E-ol 4.5 E+00 2.12 E+Ol 1.89 E+00 1.1 E+00 1.7 E-Ol Sr-90

.'8.6 mCi <3.8 E-09 2.0 E-01 E-09 <8.6 H-09 <3.7 E-nq -nr Tc-99m mCi. 4.3 E-01 2.53 E+00 3.9 E-01 7n-65 mCi (<3.0 E-08) (<9.6 E-08) (<3.2 E-08) (<3. 6 E-08) (<6. 7 E-08 <6. 1 E-08 Zr-95 mCi (<2.3 E-08) <6.6 E-08) 1.74 E+Ol <3.2 E-08 7.0 E-02 <5.0 E-nA mCi 1.92 E+Ol Unidentified mCi 1.47 E+Ol 7.75 E+00 2.2 E-01 1.01 E+Ol 2.93 E+00 Total mCi 1.78 E+Ol 6.72 E+02 3.82 E+03 2.70 E+02 6.05 E+01 6.84 E+Ol NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

I Table I Report of Radioactive Effluents: Liquids Haste Disposal System Page-4 Isotones Unit July August September October November December Ag-llom mCi 2.1 E-Ol 4.5 E-ol ~ 3.0 E-Ol Ba-140 mCi (<2.0 E-07) (<3.4 E-07) (<1.9 H-O7) (<2.7 E-O7) .(<4.s r;-o7) (<3.9 E-07)

Ce-144 mCi (<1.1 E-ol) (<1.4 E-07) (<9.0 E-08) (<1.4 E-07) (<2.3 E-07) (<1.8 E-07)

Co-58 niCi 1.1 E+00 6.9 E-01 1.67 E+00 6.2 r+oo 4.31 E+00 4. 0 E+00 ro-60 2.6 H-01 1.34 E+Ol 7.7 E-ol 1.2 F+00 1.45 H+00 1.87 E+00 Cr-51 mCi (<1.7 E-07) (<2.2 E-07) (<1.5 E-07) (<2. 2 H-07) (<3.6 H-07) (<2.9 E-07)

Cs-134 mCi (<2. 6 E-08) 3.3 H-ol . 2. 7 E-Ol 3.8 E-ol 5. 5 H-ol 2.93 H+00 Cs-136 mCi (<1.5 E-08) (<4.1 E-O8) (<l. 9 E-08) (<2.0 E-08) (< 2. 9 F.-08) (<2.9 F.-08)

Cs-137 mCi (<2. 9 E-08) 7;6 E-01 4.9 E-01 1.3 E+00 2.06 H+00 5.09 E+00 Fe-59 mCi (<3.0 E-O8) (<8.7 E-08) (<3.5 E-08) (<3. 7 E-08) (<6:0 H-08) (<5.4 E-08)

I-131 mCi 2.8 E-ol 7.6 E-ol 5.8 E+00 1.73 E+01 1.65 E+Ol 4.92 E-Ol I-133 mCi 2.1 E+00 1.0 1+00 La-140 mCi (<1. 1 E-08) (<9. 9 E-'09) (<1.4 H-o8) (<1.3 F."08) (<3. 0 F.-08) (<1.6 E-08) l fn-54 mCi 2; 7 E-02 4. 1 H-ol 1.4 E-01 9.9 E-02 2,15 H-ol 1.67 E-Ol Nb-95 mCi (<1.7 H-08) 5. 1 R-02 3,6 H-ol (<2. 2 F.-08) (<3. 2 H-O8 1.3 E-91 Sb-124 mCi 8.1 H-Ol l.l 8+00 3,3 E-01 3.4 p+On 8.26 ri+00 4.78 H+00

'Sb-125 mCi 3.0 H-ol 9.2 E-ol 2.3'-ol 1.9 E+00 3.13 H+00 2.54 F+00 Sr-89 mCi H-01 (<3.2 H-09) 4.43 E+00 E-ol 6;5 H-n2 7.0 E-02 Sr-90 mCi (<3.8 H-09) (<3.2 E-09) (<3.0 E-09) (<2. 9 E-09) (<2.9 H-09) 1.9 E-02 Zn-65 mCi (<3.0 H-08) (<9.6 E-08) (<3.2 E-08) (<3.6 E-08) (<6.7 E-08) (<6.1 E-08)

Zr-95 mCi <2.3 E-08 <6.6 E-08) (<3.2 E-08 <3. 2 H-08 <5.3 H-08 <s.o r.-08 3.1 H+00 1.86 E+Ol 1.49 E+01 3.43 E+01 3.80 F+Ol 2.21 H+01 Total mCi NOTE: Numliers in parentlie.c.. represent niaximimi sensitivity in pCi/ml.

0 Table I Report of Radioactive Effluents: Liquid Secondary System Pae5 Isotopes Unit July . August September October November December Ag-110m mCi Ba-140 mCi 4.92 E+00 C0-144 mCi Co-58 mCi 6. 1 F.-ol 1.16 8+02 5.02 K+00 2 64 E+ 1

-Co-60 mCi 2.3 E-ol 2.32 E+01 5.4 E-01 2.74 F+00 7.28 E+00 Cr-51 6.01 E+Ol 3.48 E+00 Cs-134 mCi 6.92 E+00 2.54 E+02 1.27 E+01 6.7 E-01 9.06 E-Ol T

8.7 E-01 7.32 E+Ol 9. 8 F.-Ol Cs-137 mCi 1.03 E+01 '.43 E+02 1.27 E+Ol 1.04 E+00 7. 4 E-'01 Cs-138 mCi 4.26 E+Ol 5.69 E+Ol 7.1 E+00 F-10 mCi 1.59 E+Ol 1.37 E+02 3.17 E+01 Fe" 59 mCi I-131 mCi 7.16 E+Ol 1.45 E+03 5.9 E+01 1.01 H+00 1. 5 E-01 I-132 mCi 7.95 E+Ol 8.05 E+01 8.5 E+00 4.9 E+00 I-133 1.67 H+02 8.67 E+02 4.41 E+01 4.53 1+00 I-134 mCi 8.85 E+Al 1.66 E+Ol 4.2 F+00 5.4 H-Ol

'I-135 1.44 E+02 2.17 E+02 1.04 E+01 La-140 mCi 2.42 H+00 7.2 E-01 7.6 E-02

! ln-54 mCi 3.1 E-01 4.86 E+01 3.9 F.+00 .8 F.- l.

Ho-99 mCi 8.5 E-01 2.16 E+00 1.9 E+00 Na-24 mCi 4.1 '+00 7. 95 .E+Ol 2.04 E+Ol Nb-95 mCi 1.89 E+Ol 6.0 E-01 1.5 H-01 1.8 H+00 Sb-124 mCi Sb-125 mCi

/

l fi

Table I Re ort of Radioactive Effluents: Liquid Secondary System Page 6 Isotopes Unit July August September October November December Sr-89 mCi 4. 5 E+00 1.68 E+Ol: 1.78 E+00 1.03 E+00 1.0 E-Ol Sr-90 2.0 E-Ol (<8.6 H-09) (<8.6 E-09) (<3.7 E-09) (<3.7 E-09)

Tc-99m mCi 4.3 E-01 2.53 E+00 3.9 E-01 Zn-65 mCi Zr -95 mCi 1.74 E+Ol 7.0 E-02 Rb-88 mCi 1.92 E+01 Unidentified mCi 1.47 E+01 7.75 E+00 2.2 E-01 1.01 H+Ol 2.93 E+00 To ta 1 1.47 H+Ol 6.54 E+02 3.80 H+03 2.36 E+02 2.25 H+01 4.63 8+01

Table 1 Report of Radioactive Effluents: Liquid Dissolved Gas Page 9 Total July .August September October November December Kr-85 mCi (<4.1 E-06) . (<4.6 E-06) (<3.5 E-06). (<7..8 E-06) 1.83 E+Ol (<5.1 E-Ob)

Xe-131m 'mCi (<3. 6 E-07) 3.96 E+01 6.26 E+01 (<1.8 E-06) (<3.4 E-06) (<6.8 E-07)

Xe-133 mCi 1. 7 E-01. 1.66 E+Ol 3. 0 E+02 2.38 E+01 1.87 K+02 (<4.6 E-08)

X -1'1'1m mCi <7.6 L'-08 <1.6 E-07 <1.0 E-07 <2.9 F.-07 7.1 E+00 <1.4 F.-07 Xe-135 (<7.7 E-09) 7.45 E+00 7.0 E+Ol 2.6 E+00 5.0 E+01 (<1.4 E-08)

Waste Disposal System tC -AR mCi <4.1 F.-06 <4.6 E-06 <3.5 E-06 <7.8 E-06 1.83 E+01 <5.1 F.-06 Xe-131m mCi <3.6 E-07) (<8.1 E-07) (<6.3 E-07) (<1,8 E-06) (<3 4 E"06) (<6.8 E-07 Xe-133 mCi. 1.7 E-01 3.5 E+00 E-01 1.25 E+Ol 1.83 E+02 (<4.6 E-08)

Xe-133m mCi (<7. 6 E-08) (<1. 6 E-07) (<1.0 E-07) (<2. 9 E-07) 7.1 E+00 (<1.4 E-07)

XG-135 mCi (<7;7 E-09) 8.8 E-01 (<1. 4 E-08) 2.3 E+00 4.98 E+01 (<1. 4 E-08)

Seconder S stem Kr-85 mCi

'e-131m mCi 3.96 E+Ol 6.26 E+Ol Xe-133 mCi 1.31 E+01 3.0 E+02 1.13 E+Ol 3.8 8+00 Xe-133m mCi XQ-135 mCi 6.57 E+00 7.0 E+01 2. 6 E+00 2.0 E-01 NOTE; Num ers xn parentheses represent maximum sensitive.ty xn p a m

A.'rborne Releases Airborne releases to the atmosphere occurred from release of gas decay tanks> via the instrument bleedline, containment purges, and from the secondary system during conditions of primary to secondary leakage.

The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases.

b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89-90 determination, gross alpha analysis, and gross beta-gamma analysis.

c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Condens'ation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

All sporadic gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 equivalent by use of the plant vent process monitor recorder chart.

The maximum rated capacities for the hogging jets and condenser air ejectors, and an estimate of the rate of exhaust from the atmospheric dumps was used to conservatively estimate the airborne releases from the secondary system whenever applicable.

The following comments will aid in the interpretation and evaluation of the airborne release data presented in Table II.

1. Calculation of total radioactivity for noble gases, I-131, and particulates is based upon detectable radionuclides only.
2. The applicable limit for release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calendar quarter.

13

~ ~

~ I The percent of the applicable limit for total gaseous release was computed as follows:

Total curies released in aseous waste durin auarter x 100%

(.012 Ci/sec) (seconds in quarter)

3. The applicable limit for the release of I-131 and. particulate radio-nuclides with half-lives greater than eight days in airborne waste is:

E,><

Q < 10,000 ,where m

3 Q. =

Ci/sec i

release rate of .th nuclide, and HPC i~ maximum permissible concentration of the ith nuclide.

The release rate, Q , was determined by dividing the total activity released in Ci, for the ith nuclide (tl/2 > Sd) in the calendar quarter by the seconds in the quarter.

HPCi values were obtained from Appendix B, Table II, Column 1, 10 CPP. 20. The HPC chosen was the most conservative value of either the soluble or insoluble HPC for each isotope.

The percent of the applicable limit was determined as follows:

E of Limit = 10,000 Qi HPC x 100%

m /sec

4. All values reported in Table II, page 2, include the particulate activity released from both the gas waste disposal system and the secondary system during conditions of primary to secondary system leakage. If a minimum detectable activity value was not calculated for an isotope, it will be listed as ( ).

14

5. All values for gaseous radionuclides reported in Table XE, page 3, p

include the quantity of gaseous nuclides released via the waste disposal system and secondary system.

15

lf Table II Report of Radioactive Effluents: Airborne Page 1-July August September October November December A. Fission and Activation Gases

1. Total Release (Ci) 1.11 E+03 1.49 E+03 1.51 E+03 4.31 E+03 1.91 E+03 1.57 E+03
2. Avg Rel Rate for Period (pCi/sec) 4.1 E+02 5.5 E+02 5.8 E+02 1. 6 E+03 7.4 H+02 5.8 E+02
3. Hax Rel Rate for Period (uCi/sec) 3.8 E+04 6.0 E+04 4.3 E+04 6.6 E+04 4.2 E+04 8.5 E+02 B. Iodine 131
1. To tal Iodine 131 (Ci) 1.4 E-03 8.8 E-02 5.3 E-02 3.9 E-02 4.7 E-02 1.4 E-02
2. Avg Rel Rate for Period (pCi/sec) 5.2 E-04 3.3 E-02 2.0 E-02 E-02 1.8 E-02 5.2 E-03 C. Particulates
1. Particulates with tl/2>8d (Ci) 6.21 E-05 1.09 E-02 1.11 E-02 1.42 E-02 2.10 H-02 1.04 E-02
2. Av Rel Rate for Period (uCi/sec) 2.3 E-05 4.0 H-03 4.3 E-03 5. 3 H-03 8.1 H-03 3.9 E-03
3. Gross Al ha Radioactivity (Ci) (<2.8 H-09) 4.2 E-08 (<2.1 E-09) 8. 7 E-09 1.6 E-07 5.1 E-07 D. Tritium
1. Total Release (Ci) 8.0 E-Ol 1.12 E+00 6.24 E-ol 2.0 E-01 1.5 E-01 3.3 E-03
2. Av Rel Rate for Period (pCi/sec) 3.0 H-01 4.1 H-ol 2.4 E-01 7.4 E-02 5.8 H-02 1.2 E-03 E. Percent of Applicable Limit Quarter III Quarter IV
1. Fission and Activation Gases (%) 4.3 E+00 8 2 E+00
2. I-131 and Part (tl/2>8d) (%) 1.8 E+00 1. 3 E+00

0 0

Table IX Airborne Releases Particulate Page 2 Lsotope Unit July Augus t September October November December Ag-110m Ci 1.7 E-05 Ba-140 (<1.6 E-13) 5.3 E-04 (<2.6 E-12) 1.5 E-05 (<2. 7 E-12)

Ce-141 6.5 F.-DS 1.2 E-0 Ce-144 Ci (<3.9 E-14) 1.2 E-04 (<5.2 E-13) (<6.9 E-13) 3.5 E-05 9. 5 F.-05 1 4 H-05 <4.4 E-13 2.0 H-05'.4 E-05 6.2 E-05 .1.8 E-05 Co-58 1.0 E-05 3.9 E-04 7. 1 E-03 9.0 E-03 1.8 H-.02 4.1 E-03 Co-60 Ci 2.3 E-05 1.9 E-04 1.9 E-03 1.4 E-03 5.4 E-04 3.4 E-03 Cr-51 (<1. 1 H-13) 2.4 E-04 8.3 E-04 2.7 .E-03 3.5 E-05 4.2 E-04 Cs-134 2.2 E-06 3.0 E-D3 4.5 E-04 2. 2 F.-04 3.9 E-05 (<2.8 E-13)

Cs-136 Ci (<1.2 E-$ 4) 3.5 E-04 (<1.5 E-13) (<1.6 E-13) (<2.8 E-13) (<2.4 E-13)

Cs-137 Ci 6.6 E"06 4.2 E-D3 4.5 E-05 5.7 E-05 1.0 E-04 3.2 E-05 Fe-59 Ci (<2.5 E-14) 8.D E-06 E-05 1.2 E-04 2.7 E-04 8.1 E-05 I-131 Ci 3.'? E-06 1.2 E-D3 2.3 E-05 1.1 E-04 6.7 P.-OS (<1.7 E-13)

I.a-140 Ci (<1.9 H-14) 2.0 E-04 (<5. 9 E-14) 4.3 E-D6 2.9 E-05 1.3 E-04

. Hn-54 Ci. 8.0 E-07 9.1 E-05 4.8 E-04 1,7 E-04 8.3 E-04 2.0 E-04 Nh-95 (<1.6 H-14) 2.4 H-05 8.9 E-05 1.5 E-04 3.3 E-04 1.1 E-03 Ru-103 1.0 E-06 8.0 E-05 -

(<2.1 E-13) (<2.8 E-13) 2.0 E-04 3.8 E-04 Sb-124 (<2.1 H-14) 6.6 E-06 l. 2 E-O5 7.1 E-05 6.3 . E-05 2,1 E-05 Sb-125 Ci (<3.7 E-14) (<3. 1 H-12) '<5. 1 E-13) (<6. 7 P.-13) (<8.3 E-13) E-13) '<5.4 Sr-89 Ci 1.2 H-D6 1.9 H-04 3.2 8=06 2.2 E-06 2.2 H-OS 1.1 H-05 Sr-90 F- F.-D 7,n-65 Ci <3.7 E-14 < l. 9 E-12 2.2 E-05 2. 9 F.-05 1.5 H-04 8.7 P.-05 zr"95 Ci (<2.5 E-14) 2. 1 E-05 4. 1 E-05 1, 2 E-04 1.8 E-04 2.4 E-04 Total Ci 6.21 H-DS 1.09 E-02 1.11 H-02 1.42 E-02 2.10 H-02 1.04 E-02 Ph 'ill

~ i + ~ ~l iI iiiit i~

I

'in ><C4 /

0 I

Table II Airborne Releases Gaseous Page 3 .

Fission and Activation Gases Isotope Unit "July August September October November December E-01 8.9 E-01

'.7 Ar-<<l E+00 1.16 E+Ol 7.8 E+00 8.42 E+00 7.7 Kr-85 5.3 E-01 7.7. E-Ol 4.0 E-01 (<2.9 E-05) 3.3 E-01 4.0 E-01 Kr-85m Ci 2.7 E-01 6. 2 E+00 '6.73 E+00 1.51 E+00 7.1 E-Ol 4.5 E-06 Kr-87 1.3 E-02 7. 7 E+00 8.52 E+00 1.77 E+00 '.6 E-02 (<4.7 E-07)

Kr-88 Cj 6.7 E-ol 7.3 = E+00 1.02 E+Ol 2.25 E+00 5.0 E-01 <8.7 E-07)

Xe-131m Ci 1.0 E-02 1.6 E-01 3.1 E-02 (<3.9 E-06) 1.5 E-01 2.2 E-01 XG-'133 Ci 1.08 E+03 1.32 E+03 1.40 E+03 4.27 E+03 1.89 E+03 1.57 E+03 Xe-133m Ci 4.95 E+00 6.6 E+00 6.39 E+00 4.6 E+00 5.0 E+OO 7. 2 E-03 Xe-135 Ci 1.93 E+Ol 5.95 E+01 5.13 E+Ol 1.92.E+01 1.43 E+01 1.4 E-04 Xe-135m (<9.7 E-07) 4.39 E+Ol 8.85 E+00 1.95 E+00 (<3.7 E-06) (<4. 6 E-07)

Xe-138 (<7.0 E-06) 2.56 E+01 1.02 E+01 2.0 E+00 (<3.8 E-05) (<8.4 E-07)

DENOTE:

Total Ci 1.11 E+03 1.49 E+03 1.51 E+03 4.31 E+03 ~ 1.91 E+03 1.57 E+03 Numbers in parentheses represent maximum sensitivity in yCi/cc.

Nalogens (Gaseous)

'Isotope July August September October November December I-131 1.4 E-03 8.7 E-02 5.3 E-02 3.9 E-02 4.7 E-02 1.4 E-02 I-133 Ci 3.0 E-O<< 8.9 E-02 1.6 E-03 1.2 E-02 4.8 H-03 3.8 H-05 I-135 (<5.7 E-14) 2.4 H-02 5.2 E-04 1.6 E-03 (<2.3 E-13) (<l. 9 E-13)

1. 7 E-03 2.0 E-Ol 5.5 E-02 5.3 E-02 5.2 E-02 1. <<E-02

.Total

RADIOACTIVE PASTE July 1 to December 31, 1976 Packed Ci Cu. Ft ~

Total 380 .236 300946,75 On site as of January 1, 1977 1.082 2,005.95 Ehtes of Shipment and Disposition 13 July, 1976 Buried in Barnwell, South Carolina 19 July, 1976 27 July, 1976 29 July, 1976 13 August, 1976 16 August, 1976 20 August, 1976 2 Sept., 1976 3 Sept., 1976 U. Sept., 1976 17 Sept., 1976 19 Sept., 1976 19 Sept., 1976 20 Sept., 1976 21 Sept., 1976 23 Sept., 1976 28 Sept- 1976 30 Sept., 1976 5 Cct., 1976 5 Oct., 1976 22 Oct., 1976 23 Oct., 1976 27 Oct., 1976 28 Oct , 1976 1 Nov., 1976 2 Nov., 1976 4 Nov., 1976 8 Nov., 1976 22 Nov., 1976 26 Nov., 1976 29 Nov., 1976 29 Nov., 1976 19

RADIOACTIVE WASTE July 1 to December 31, 1976 Page 2 Dates of .Shipment and Disposition 1 Dec., 1976 Buried in Barnwell, South Carolina 5'ec., 1976 8 Dec., 1976 8 Dec., 1976 13 Dec., 1976 14 Dec., 1976 18 Dec., 1976 18 Dec., 1976'.

21 Dec., 1976 22 Dec., 1976 23 Dec., 1976 27 Dec., 1976 29 Dec., 1976 TOTAL~ 45 SHIPMENTS 20

TURKEY POINT UNITS 3 & 4 RADIOLOGICAL ENVIRONMENTAL MONITORING During this report period, 7-01-76 to 12-31-76, radiological surveillance at Units 3 and 4 was carried out by the Orlando Radiological Laboratory of the Department of Health and Rehabilitative Services of Florida. All samples were collected and analyzed in accordance with Units 3 and 4 Technical Specifica-tions ~

A total of 725 samples from 33 different sampling locations were collected and analyzed. Table REM-1 summarizes the mean and range values of these analyses. Since 40 K, 226 Ra and 232 Th are naturally occurring radionuclides, no data for these species are recorded in this table. The gross beta data reported is repre-sentative of these and other naturally occurring radionuclides.

Table REM-2 reports on those sampling locations that showed evidence of having concentrations of a particular radionuclide in a specific sample material higher than that observed mean for that radionuclide at all sampling locations. However, none of. these concentrations exceed the limits established by Appendix B, Table II, 10 CFR 20.

The data recorded in Table REM-2 can be analyzed in this manner:

3 a) H concentrations at sampling locations T-84 and T-97 continue at levels consistent with those reported in previous Semiannual Reports.

b) Similarly, the GB and 3 H concentrations at sampling location T-75 do not show significant increases above those data reported in other Semiannual Reports.

c) Low ground water levels and temperature and salinity differences are still 3

viewed as the continuing factors to the levels of H in the Ground Hater Hells at 21

c) Continued locations T-87, T-88, T-91 and T-92.

d) The concentration levels of 58 Co, 60 Co, 95 Zr and 54 Mn in the discharge canal (T-84) are of the same order as those previously reported.

e) The 90 Sr data reported for sampling location T-52 are based solely on 1 or 2 assays of a food crop and a soil sample. The validities of such data are not marked~by a high degree of precision.

f) All data observed on samples collected and analyzed during October-December, 1976 reflect some influence from the Chinese bomb tests of that period.

The Orlando Laboratory has continued its Split Sampling Program with ERDA's HSL. Typical comparative data for Turkey Point air particulate samples analyzed in this program follows (Table A). A similar group of data (Table B), comparing the Orlando Laboratory work with that of the US EPA ERAMS station in Miami, is also included in these tabulations. A summary (Table C) of the trehds observed in the Mean and Range values for Air Particulates 'and TLD's samples during 1974-76 is also submitted as a part of our data package for this report period.

22

0 TABLE A TURKEY POINT: COMPARISON OF CONCURRENT AIR PARTICULATE SAMPLES 3

(pCi/m )

Date U.S. ERDA HASL DHRS Sample (NRC' lit) (T-58) (T-58) 11-,20-74 0. 08 0. 07 11-27-74 0. 123 0.13 12-'05-74 0.114 0.14 12-11-74 0.22 0.26 3-19-75 0.139 0.13 3-27-75 0.201 0.19 4-02-75 0.137 0.15 4-10-75 0.24 0.31 5-02-75 0.081 0.07 5-29-75 0. 065 0. 06 6-05-75 0. 045 0. 03 6-12-75 0. 068 0. 05 11-19-75 0.027 0. 011 11-27-75 0.038 0. 022 12-03-75 0.035 0.022 12-11-75 0.023 0.022 23

TABLE B COMPARISON OF TURKEY POINT NETWORK AVERAGE (b Month)

(With U.S. EPA Environmental Radiation Monitoring Systems [ERAMS]

Miami Station Mean [Range] pCi/m )

Date Single Station Miami Mean of 8 Stations ERAMS DHRS Turke Point August 1974 . 0.08 (0.04 to 0.14) 0.14 (0.08 to 0.23)

September 1974 0.03 (0.02 to 0.07) 0. 06 (0. 02 to 0. 13)

October 1974 November 1974 December 1974

0. 04 (0. 02 to 0. 07) 0.06. (0.04 to 0.08) 0.07 (0.05 to 0.10)

'.10 0. 05 (0. 02 to 0. 08)

(0.05 to 0.46)

0. 15 (0. 07 to 0. 26)

January 1975 0.07 (0.04 to 0.12) 0.14 (0.08 to 0.22)

February 1975 0.13 (0.03 to 0.55) 0 14 (0. 09 to 0. 20)

March 1975 April 1975 May 1975 0.11 (0.08 to 0.15)

0. 10 (0. 06 to 0.

0.06 (0.03 to 0.08) 16), 0.21 (0.13 to 0.30)

0. 18 (0. 11 to 0. 33) 0.09 (0.02 to 0.08)

June 1975 0. 02 (0. 01 to 0. 04) 0.04 (0.01 to 0. 08)

July 1975 0. Ol (0. 01 to 0. 02) '

0. 03 (0. 002 to 0; 12)

August 1975 0.01 (0.01 to 0.02) 0.02 (0.003 to 0.05)

September 1975 <. Ol (<. Ol to 0. 02) 0. 02 (0. 004 to 0. 04)

October 1975 <.Ol (<.01 to 0.01) 0. Ol (0. 005 to 0. 025)

November 1975 <.Ol (<.01 to 0.02) 0. Ol (0. 003 to 0. 035)

December 1975 0. 01 (<. Ol to 0. 03) 0. 02 (0. 001 to 0. 07)

It can be seen that the Turkey Point network mean closely follows the results of the U.S. EPA ERAMS station in Miami. It can further be seen that results of split samples during the period show no significant.

difference.

24

TABLE C TURKEY POINT" TREND ANALYSIS (Mean and Ran e C-l. -Air Particulates Ci/m3 1974 Mean all Stations 1975 Mean all Stations 1976 Hean all Stations tr 2 tr 3 tr 4 tr 2 tr 3 tr 4 t1 2 tr 3 tr 4

0. 126 0. 218 0. 099 0. 097 0.16 0.10 0.020 O. 015 0.012 0.013 NA NA 0.038 to 0.10 to 0.00 to 0.02 to 0.07 to 0.002 to 0.01 to 0.001 to 0.003 to 0.000 to 0.250 0.80 0.23 0.26 0.32 0.33 0.05 0.070 0.040 0.030 Control Location (T64) 0.14 O. 24 O.ll 0.10 0.16 0.11 0.026 0.015 0.014 0. 014 NA NA 0.02 to 0.10 to 0.03 to 0.04 to 0.04 to 0.03 to 0.005 to 0.003 to 0.008 to 0.000 to 0.29 0.40 0.23 0.22 0.31 0.30 0.05 0.030 0.025 0. 027 C-2. TLD Dose mR/hour 1974 Mean all Stations 1975 Mean all Stations 1976 Hean all Stations t1 2 tr 3 tr 4 tr 2 tr 3 tr 4 tr 2 tr 3 tr 4
0. 004 0. 005 0. 004 0. 004 0.004 0.005 0.005 o.oo5 0.004 0.005 NA NA 0.003 to 0.003 to 0.003 to 0.002 to 0.002 to 0.002 to 0.003 eo 0.002 to 0.003 to 0.004 to
0. 006 0.006 0.006 0. 007. 0.005 0.007 0,007 0,007 0.006 0.006 Control Location (T64) 0.005 0.004 0.005 0.005 0.004 0.005 0. 006 0.006 0.005 0.005 NA NA NA=data not available

I TABLE RHM-1:

RADXOLOGICAL ENVIRONMENTAL Facility Turke Point-Units 3 & 4 Docket Numbers 50-250, -251 MONITORING .

Program Summar Location Dade County, Florida Reporting Period 7-01-76 to12-31-76 MEDIUM OR ANALYSIS ALL SAMPLE LOCATIONS PATHWAY SAMPLED PERFORIIED (Units) LLD PRE-OP 1976 1975-76 Type Number BG MEAN RANGE MEAN RANGE

l. Air Filters
l. 1 Air Particulates 3 0.002 0.01 0.011 0.009- 0. 0155 .003-0.04 (pCi/m ) 222 0.012e l.lA Air Xodines (pCi/m 3 131I 214 0.008 0.01

)

1.2 Direct Radiation

-TZD s (IjI~7I~) 131 0. 05 4.9 4-6 4 4-6

l. 3 Precipitation (pCz 1 GB (DS) 24 0.8 12g 10-12g 1-7 GB(UDS) 24 0.8 4g ND"7 H 199 <200 <200 <200
2. Water KX Estaurine (pCi/1) H 20 199. <200 <200 <200 89 Sr 20 1.6 (1 6)h "Sr 20 0.8 (0.8)

PIIGB 2 (>f

'I'III3I.I: Ill:33-3. (C~Ont'd Ml':DXUM OR ANALYSXS ALL SAMPLL LOCATXONS PA I'IIHAY SAMPLL'D PH RFORl 11;D (Units) LLD Plier;-OP 1976 1975-76 Number BG MI"AN RAiUGI'ANl1RAN GI".

2. Water (Cont'd)
2. 2 Coolin Canal (pCx 1 H 199. <200 4,370 3200- 3,950 3200-6000 6000 89 Sr 14 1.6 (1.6) 90SSr 14 0.8 (0.8) 2.3 Fresh Water Canals

~

(pCi 1) GB (DS) 12 0.8 184 ND-870 188 ND-570 CB(UDS) 12 0.8 H 12 199. <200 358 <200-1000 424 <200-620 2.4 Potable Wells

.(pCi 1) GB 0.8 5. 4-8 ND-ll H 199. <200 <200 <200 2.5 Ground Water Wells (pCi 1) H 12 199 <200 960 <200-2100 799 <200-1800 89 1.6 (1. 6) 12 90SSr 12 0.8 (0. 8)

3. Sediment

.l. ~1 (pCi/kg) 58Co 95 ND-190 85 ND-170 60Co 110 ND-220 60 ND-120

0 PAGE 3 I'AII).l'. Ill:I{-1 {c~OnL'd Ml. D.fljM OR ANALYSIS ALL SAMPLH LOCATXONS I'A'I'1lblAY SAMPLED PHRFORMHD (Un3. ts) LID P RH-OP 1976 197 5-76 Tppe Number 13G MEAN RANCH MHAN RANGH

3. Sediment (Cont'd) 95 Zr 45 ND-90 40 (Cont'd) 54 105 ND-210 ND 89 Sr 1.6 (1. 6) 90S 0.8 (0. 8)
3. 2 Hstaurine 89SSr 1.6 (1. 6)

((~i kg)

OSSr 0.8 (0. 8) 4.1 Crustacea 89

~/pCi g) Sr 10 (8) 90 ND-41 Sr 10 (4) 8

4. 2 Fish-Carnivore 89 (pCz g) Sr (8) 90S (4) 4.3 Fish-Herbivore 89 (pCi g) Sr 13 (8) 90 (4) 12 ND-12 13 4.4 Manatee Grass 89 Sr 1.6 (1. 6) 89 ND-89 pCi kg 90 0.8 (0. 8)

PAGE 4 of 4

'I'331333'. I'I'.31-3. (C~Ont'd MHDIUM OR ANALYSIS ALL SAMPLH LOCATIONS PA'1'ill')AY SANPLHD PHR)"ORMHD (l)ni ts) LLD 1'Rl"-OP 197 197 -7 Type Number 13G MEAN RANGH Ml'.AN RANGE

'N

4. 5 gSmn~es (pCi/kg) 60Co 130 ND-130 39 ND-190 144CCe 340 740 ND-740 1,172 ND-4300
5. Terrestrial Biota 5.1 Small Animal 89 Sr (8) NDk (pCi/kg) 90 63 (4) 5.2 ~Food Cro 89 (pCi/kg) Sr (5) 90 221 26 ND-30 Sr (2) 5.3 Mangrove Leaves 89SSr (5)

(pC> g) 30 ND-45 90 ND-16 ND-26 (2) 7n ND-19 5.4 Soil 137CCs (pCi/Kg) 26 (26) 278 ND-630 353 ND-670 89 Sr (5) 90SSr (2) 23 ND-160 ND-180

0 TABLE REM-1 NOTES

a. LLD = nominal limits of detection as defined in HASL (Rev.

8/73) D-08-1 to -3.

b. Where applicable, mean proportional BG data is derived from analyses made during the period 1-01-72 to 12-31-72.
c. For the period 7-01-76 to 12-31-76.
d. For the period 7-01-75 to 6-30-76.
e. (1) July-September, 1976 data used here. Chinese bomb fallout accumulations impacted October-December, 1976 data to give these results (pCi/m3) for all locations, except Control Sample T-64.

October November December Mean 1.21 0.22 0.037 Range (0.13-2.9) (0.07-0.40) (0.02-0.05)

(2) Control Sample, T-64, showed these results (pCi/m 3 ):

July-Se tember October November December Mean 0. 012 2.19 0.24 0.035 Range (0.009-0.02) (0. 22-6. 7) (0. 009-0. 40) (0. 03-0. 05)

f. Based on July-September observations. Following Chinese bomb fallout accumulations, these data. were recorded:

131 I = 0.08 pCi/m. 3 3 (av. amount of air collected)

Av per 2332 m 137 Cs = 130 + 1 pCi/m 3

g. All data for July-September, 1976 recorded as "ND". Data shown in tabulation observed after Chinese bomb fallout accumula-tions.
h. ( ) = No radioactivity detected in Pre-Op analysis. All values appearing in ( )'s are LLD's used as estimates of Pre-Op BG.

One sample collected in November, 1976, after Chinese bomb fallout accumulations. This sample also contained:

131 1 = 130 + 70 pCi/kg 140 Ba = 300 + 100 pCi/kg 30

TABLE REM-1 NOTES (Cont ')

(Cont'd) 106 Ru =

900 + 200 pCi/kg 95 Zr = 270 + 70 pCi/kg

j. Used HASL computation method to determine this value.
k. 1 Rabbit sample only.
l. 1 Malanga sample only.
m. July-September, 1976 data only.
n. On samples collected after Chinese bomb fallout accumulations.

31

~ I TABLE RHM-2:

Facility Turke Point Units 3 & 4Docket Number (s) 50-250 -251 .

SAMPLING LOCATXONS WXTII IIXGEIHST ANNUAL MEAN Location Dade Count Florida Report Per iod7-01-76 tol2-31-76 MEDIUM OR LOCATION 'WITH IIIGHHST ANNUAL MEAN PATHWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976 1975-76 (UNITS) FOR OF (RANGE ) IIIGH SITE .

.MEAN RANGE MEAN RANGE SXTES SITES Control location

a. Air P~culates (pCi/m ) 0. 012 (0. 008-
0. 020)
b. Direct Radiation v ) 5 (4-6)
c. Preci itation (pCi 1) 15 (ND-19)

EK <200

l. Air Filters 1.1 Air Particu-lates (pCi/m )

7h 0. 011 All locations had (0. 009- no significant

0. 012) deviations from Mean of Control Sample

TABLE REM-2 (cont'd) PAGE 2 Of S.

r MEDIUM OR LOCATXON NX'1'H IIXGHHS'1'NNUAL MEAN PATIIWAY SAMPLED ANALYSIS NUMBI"R MEAN NUMBER 1976 1975-76 (UNX'1'S) FOR or (RANGE ) HX GII SXTH MEAN RANGE MEAN RANGE SITES SITES

1. Air Filters (Cont' 1.1A Air Iodines (pCi/m 131I

)

1.2 Direct Radia-tion-TID' (pRem/hr) 4,9 0 1 locations had n (4-6) -ignificant devia-.

tions fran Mean 1.3 Preci itation (pCi 1) 1 locations had n ignificant devia-ions frcm Mean GB(DS) 12 0 1 locations had n (10-12) ignificant devia-ons from Mean GB(UDS) 4 1 locations had n (ND-7) ignificant devia-tions fran. Mean H. (200 1 locations had n significant devia-tions from Mean

2. Water 2.1 Hstaur1ne (pCi/1) 10 1 locations had n significant devia-tions frcm Mean

TABLE RHM-2 (cont'd) PAGE 3 of ~

MEDIUM OR LOCATION NITH IIIGIIHST ANNUAL MEAN PATIlNAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976 1975-76 j (UNITS) FOR OF (RANGE) 1IIG/1 SITE MEAN RANGE MEAN RANGE SITES SITES

2. Water (Cont'd) 2.1 Hstaurine (Con 'd) 89 Sr 10 All locations had no significant deviations from Mean 90 Sr 10 All locations had no significant deviations from Mean
2. 2 Coolin Canal (pCi 1) -H 4,370 T-84:Discharge 4,420 3,200- 4,216 3,200-(3,200- Canal, south side 6,000 6,900 6,000) of bridge, on-site T-97:Loch Rosetta, 4,320 3,300- 3,900 3,400>>

on-site 5,100 5,100 89 Sr 1 All locations had (ND-1) no significant deviations frcm Mean Sr 1 0 All locations had (ND-1) no significant deviations from Mean 2.3 Fresh Mater Canals (pCi/1) GB(DS) 184 T-75:Florida City 363 230-870 388 290-570

{ND-870) Canal, east of dam

0 TABLE REM-2 (cont'd) PAGE 4 of e MEDIUM OR LOCATION WITII IIIGIIHST ANNUAL MEA5 PATIIWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER (UNITS) POR OF (RANGE) IIIGH S ITL'976 1975-76 MEAN RANGE MEAN RANGE SITES SITES

2. Water (Cont'd) 2.3 Fresh Water Canals (ContB)

GB(UDS) All locations had no significant deviations from Mean H 358 T-75:Florida City 475 <200- 372 <200-620

(<200- Canal, east of dam 1,000 1,000) 2.4 Potable Wells

~tfC 6 T-57:Dolan's Farm 7-8 10 8-11 (4-8)

T-73:City of 7-7 Hcmestead Waker System H <200 All locations had no significant deviations fran Mean 2.5 Ground Water Wells (Qx71) H 960 T"87:Well E-10 1,800 1,500- 1,460 1,400-(<200- 2,100 1,520 2,100)

T-88:Well E-14 1,400 1,300- <200 1,500

al TABLE REM-2 (cont'd) PAGE 5 of 9 MEDIUM OR LOCATION WITII IIIGHHST ANNUAL MEAN

  • PATI1WAY SAMPLED ANALYSIS NUMBER MEAN NUMI3HR 1976 1975-76 (UNITS) FOR OF (RANGE) IIIGII SITE MEAN RANGE MEAN RANGE S I'THS SXTES
2. Water (Cont'd) 2.5 Ground Water Wells (Cont'd)

T-91:Well G10A 1,050 1,000- 930 800-1,060 1,100 T-92:Well G24A 1,700 <200- 1,620 1,600-1,700 1, 640 89SSr All locations had no significant deviations from Mean 90SSr All'ocations had no significant deviations from Mean

3. Sediment 3.1 Coolinq Canal 58 ND-190 95 T-84:Discharge 190 190-190 85 (pCi/kg)

(ND-190) Canal, south side of on-site bridge "Co 110 T-84:Discharge 220 220-220 120 120-120 (ND-220) Canal, south side of on-site bridge 95 T-84:Discharge 90-90 Zr 45 (ND-90) Canal, south side of on-site bridge

TABLE RHM-2 (cont, ') PAGE 6 of 9 MEDIUM OR LOCATION WITII flIGflEST ANNUAL MEAN PATIIWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976 1975-76 (UNITS) FOR or" (RANGE) IIIGII SITE MEAN RANGE MEAN RANGE SITES SITES

3. Sediment (Cont'd) 3.1 Coolin Canal (Cont'd 105 T-84:Discharge 210 210-210 (ND-210) Canal, south side of on-site bridge 89 Sr All locations had no significant deviations fran Mean 90 Sr All locations had no significant-deviations fran Mean 3.2 Estaurine 89

~/qadi g) Sr All locations had no significant deviations from hhan 90S All locations had no significant deviations from Mean

4. Aquatic Biota

~

4.1 Crustacea

~(pCx g All locations had no significant deviations fran Mean

TABLE REM-2 (cont'd) PAGE 7 of g'EDXUM OR LOCATXON HXTII IIXGIIEST ANNUAL MEAN PATIIMAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976 1975-76 (UNXTS) FOR OF (RANGE) IIXGII SXTE MEAN RANGE MEAN RANGE SXTES SXTES

4. l Crustacea (Cont' )

90SSr All locations had no significant deviations from Mean 4.2 Fish-Carnivore 1 g

89S All locations had no significant deviations from hlean 90 Sr All locations had no significant deviations from Mean 4.3 Fish-IIerbivore (pCi g) 89SSr All locations had no significant deviations from Mean 90 12 All locations had (ND-12) no significant deviations fram Mean 4.4 Manatee Grass (pCx g 89 Sr All locations had no significant deviations free Mean

E e

TABLE REM-2 (cont'd) PAGE 8 of MEDIUM OR LOCATION WXTII IIXGIIHST ANNUAL MEAN PATIIWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976 1975 -76 (UNITS) POR OF (RANGE) IIIGII, SITE MEAN RANGE MEAN RANGE SITES SXTHS

4. Aquatic Biota(Cont'.4 IIanatee Grass (Cont'd) 90SSr All locations had no significant deviations from Mean 4.5 ~nenes 60 (pci/kg) 130 All locations had (ND-130) no significant deviations from Mean 144Ce 740 All locations had (ND-740) no significant

'deviations fran Mean

5. Terrestrial Biota 5.1 Small Animal 89 89 (pci g) Sr not found at this location 90S 90 Sr not found at this location V

5.2 Food Cro 89 89 (pci ) Sr Sx not found at this 'location 90 Sr 22 T-52:Florida City 22 ( analysi~) 29 ( analysis) 1 analysi ) Suustation-Palm Drive

~ I' TABLE REM- 2 ( cont

' )

PAGE 9 0of MEDXUM OR WXTII IIIGIIHST ANNUAL MEAN 0 1975-76'OCATION PATIIWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976 (UNXTS) FOR OF (RANGE) IIIGII SXTE MEAN RANGE MEAN RANGE SITES SXTES

5. Terrestrial Biota Cont'd) 5.3 Mangrove Leave

-(pCi g) 89S Except as noted in Note f, these locations showed no 89Sr 90S Except as noted in Note f, these 1~p.ons showed no - Sr 5.4 Soil

~pC1/kg) 137C 278 All locations had (ND-630) 'no significant deviations from Mean 89SSr All locations had no significant deviations fram Mean 90 T-52:Florida City 160 160-160 180 180-180 23 (ND-160) Substation-Palm Drive

lg v

NOTES

.a. From Table REM-1 and State of Florida Division of Health reports for 3rd and 4th quarters, 1976 (7-01-76 to 12-31-76).

b. For the period 7-01-75 to 6-30-76.
c. Number of sampling locations used to obtain data.
d. Number of sites above Mean value of data reported for the period 7-01-76 to 12-31-76.
e. T-64, FPL's Natoma Substation (ENE, 30 miles); relevant only to Air Particulate, Direct Radiation and Precipitation analyses.
f. July-September data only; October-December data reflect Chinese bomb fallout accumulations see Table REM-l.
g. NA=not applicable; ND=not detected.
h. Does not include Control Sample, T-,64.

41

g1 II II Ol (g V

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